ASTM E1005-21 PDF
Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 11
- Дата публикации:
- 1 сентября 2021 г.
- Издание:
- E1005
- ICS:
- 17.240
SIGNIFICANCE AND USE 5.1 Radiometric monitors shall provide a proven passive dosimetry technique for the determination of neutron fluence rate (flux density), fluence, and spectrum in a diverse variety of neutron fields. These data are required to evaluate and estimate probable long-term radiation-induced damage to nuclear reactor structural materials such as the steel used in reactor pressure vessels and their support structures. 5.2 A number of radiometric monitors, their corresponding neutron activation reactions, and radioactive reaction products and some of the pertinent nuclear parameters of these RMs and products are listed in Table 1. Table 2 provides data (37) on the cumulative and independent fission yields of the important fission monitors. Not included in these tables are contributions to the yields from photo-fission, which can be especially significant for non-fissile nuclides (2-5, 27-29, 38-41). (A) All yield data are given as a percentage with associated uncertainties given as percentages of the percentage at the 1σ level.(B) For this fission yield evaluation (37), “Fast” indicates that the data was extracted from a wide range of reactor-based fission neutron spectra that can be characterized as having an average energy of ~0.4 MeV. Almost all of the fission reactions for U-238 and Th-232 occur above an effective threshold energy of ~1 MeV and, for Np-237, above ~0.2 MeV. SCOPE 1.1 This test method describes procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs (1-5).2 The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs (1-29). 1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-26). 1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates (2-5, 28-30). 1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable computer programs (2-5, 28-30). 1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate (2-5, 28-30). 1.2 This test meth...
Abstract
Overview
ASTM E1005-21 – Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance provides procedures for determining neutron fluence rate, fluence, and spectrum using radiometric monitors (RMs). These passive dosimetry techniques play a critical role in the surveillance of nuclear reactor vessels and support structures, enabling the evaluation and estimation of long-term radiation-induced damage to structural materials such as reactor pressure vessel steel.
The standard details measurement methods involving gamma-ray spectrometry, X-ray spectrometry, and beta particle counting, as well as the necessary corrections and calculations to ensure high accuracy and reliability. This foundational test method is intended to support safety and longevity in nuclear power plant operation by delivering robust data for analyzing the irradiation environment and predicting material performance over time.
Key Topics
Passive Dosimetry for Reactor Surveillance
- Utilizes radiometric monitors (foils or dosimeter samples) to passively record neutron exposure within reactor environments.
- Determines neutron fluence rate (flux density), total neutron fluence, and neutron energy spectrum for accurate assessment.
Measurement Procedures
- Principal method: high-resolution gamma-ray spectrometry.
- Supplementary methods: X-ray photon spectrometry and beta particle counting for specific radiometric monitors.
- Includes corrections for background radiation, geometry differences, detector efficiency, self-absorption, decay, and nuclide burn-out.
Data Analysis and Calculations
- Converts measured specific activities into reaction rates, which can then define neutron fluence rate and spectrum.
- Uses benchmark neutron fields to calibrate radiometric monitors, reducing systematic uncertainties by direct comparison with certified standards.
- Relies on computer programs and reference nuclear data for spectrum unfolding and advanced analysis.
Quality Assurance and Calibration
- Emphasizes the use of national and certified radioactivity standard sources for instrument calibration.
- Requires regular control checks to maintain system consistency and reliability.
Applications
ASTM E1005-21 is essential in:
- Nuclear power plant surveillance – Monitoring the irradiation environment to assess and forecast radiation-induced shifts in reactor pressure vessels and their support structures.
- Material integrity evaluations – Providing critical data for estimating material embrittlement and lifespan extension strategies.
- Compliance with safety regulations – Supporting utilities and regulators with standardized, validated methods for routine surveillance and reporting.
- Benchmark testing and interlaboratory comparisons – Ensuring consistency and traceability of dosimetry across facilities through benchmark neutron fields and round-robin calibration.
By establishing robust and repeatable practices, this standard helps nuclear operators maintain safe reactor performance, optimize maintenance, and comply with regulatory requirements.
Related Standards
ASTM E1005-21 is integrated within a comprehensive framework of ASTM standards for reactor dosimetry and vessel surveillance, including:
- ASTM E844 – Guide for Sensor Set Design and Irradiation for Reactor Surveillance
- ASTM E853 – Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results
- ASTM E693 – Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
- ASTM E185 – Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels
- ASTM E1035 – Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
- ASTM E261, E262, E263, E264, E265, E266, E523 – Test methods for specific neutron activation reactions in various elements
- ASTM E944 – Guide for Application of Neutron Spectrum Adjustment Methods
- IEEE/ANSI N42.14 – Calibration and Usage of Germanium Detectors for Gamma-Ray Emission Measurement
By referencing and supplementing these related standards, ASTM E1005-21 ensures broad compatibility and consistent application across the nuclear industry, enhancing reactor safety and performance monitoring.
Optimize reactor surveillance and dosimetry with ASTM E1005-21 – your essential standard for accurate, reliable neutron field characterization and material performance assessment in nuclear power plants.
Технические детали
- Технический комитет
- E10 - Nuclear Technology and Applications
- SKU
- ASTM E1005-21
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